Measurement of Safety Injection Fluid Transport in a Scaled Reactor Test-Reference-Cited by-同舟云学术

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Measurement of Safety Injection Fluid Transport in a Scaled Reactor Test

Published:1999-03 Issue:3 Volume:131 Page:426-438
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Radcliff T. D.¹,Parsons J. R.²,Johnson W. S.²,Ruggles A. E.³

Affiliation:

1. University of Akron, Department of Mechanical Engineering, Akron, Ohio 44325-3903

2. University of Tennessee, Department of Mechanical and Aerospace Engineering 414 Dougherty Hall, Knoxville, Tennessee 37996

3. University of Tennessee, Department of Nuclear Engineering 305 Pasqua Engineering Building, Knoxville, Tennessee 37996

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE99-A2044

Reference9 articles.

1. “Draft Safety Evaluation Report Related to the Certification of the AP600 Design,” NUREG-1512, U.S. Nuclear Regulatory Commission (1994).

2. Visualization of the Lower Plenum Anomaly in the Westinghouse AP600 Reactor

3. Turbulent mixing of coaxial jets

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Experimental and Numerical Investigations on Heat Transfer of Reactor Internals Under Direct Injection;Nuclear Science and Engineering;2018-02-26

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